IR 05000275/2017007

DCPP - Inspection of the Implementation of Mitigation Strategies and Spent Fuel Pool Instrumentation Orders and Emergency Preparedness Communication/Staffing/ Multi Unit Dose Assessment Plans - Inspection Report (05000275/2017007 and 050003

ML18025A000
Person / Time
Site:	Diablo Canyon
Issue date:	01/24/2018
From:	Mark Haire NRC/RGN-IV/DRP/RPB-A
To:	Welsch J Pacific Gas & Electric Co
Haire M
References
IR 2017007
Download: ML18025A000 (18)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION

REGION IV

1600 E. LAMAR BLVD.

ARLINGTON, TX 76011-4511 January 24, 2018 Mr. James M. Welsch, Vice President, Nuclear Generation and Chief Nuclear Officer Pacific Gas and Electric Company Diablo Canyon Power Plant P.O. Box 56, Mail Code 104/6 Avila Beach, CA 93424 SUBJECT: DIABLO CANYON POWER PLANT, UNITS 1 AND 2 - INSPECTION OF THE IMPLEMENTATION OF MITIGATION STRATEGIES AND SPENT FUEL POOL INSTRUMENTATION ORDERS AND EMERGENCY PREPAREDNESS COMMUNICATION/STAFFING/ MULTI-UNIT DOSE ASSESSMENT PLANS -

INSPECTION REPORT (05000275/2017007 AND 05000323/2017007)

Dear Mr. Welsch:

On December 27, 2017, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Diablo Canyon Power Plant, Units 1 and 2. On December 27, 2017, the NRC inspectors discussed the results of this inspection with Mr. C. Murry, Acting Station Director, and other members of your staff. Inspectors documented the results of this inspection in the enclosed inspection report.

The inspection examined activities conducted under your license as they relate to the implementation of mitigation strategies and spent fuel pool instrumentation orders (EA-12-049 and EA-12-051) and Emergency Preparedness Communication, Staffing, and Multi-Unit Dose Assessment Plans, your compliance with the Commissions rules and regulations, and with the conditions of your operating license. Within these areas, the inspection involved examination of selected procedures and records, observation of activities, and interviews with station personnel.

Based on the results of this inspection, no findings of significance were identified.

In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, Public Inspections, Exemptions, Requests for Withholding, a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRCs Public Document Room or from the Publicly Available Records (PARS) component of the NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Sincerely,

/RA/

Mark S. Haire, Chief, Project Branch A Division of Reactor Projects Docket Nos. 50-275 and 50-323 License Nos. DPR-80 and DPR-82

Enclosure:

Inspection Report 05000275/2017007 and 5000323/2017007 w/ Attachment: Supplemental Information

REGION IV==

Docket: 50-275 and 50-323 License: DPR-80 and DPR-82 Report: 05000275/2017007 and 05000323/2017007 Licensee: Pacific Gas and Electric Company Facility: Diablo Canyon Power Plant, Units 1 and 2 Location: P.O. Box 56, Mail Code 104/6 Avila Beach, CA 93424 Dates: November 13 through December 27, 2017 Inspectors: J. Mateychick, Senior Reactor Inspector (Team Leader)

C. Newport, Senior Resident Inspector R. Alexander, Senior Project Engineer E. Uribe, Project Engineer Approved Mark S. Haire Chief, Project Branch A By: Division of Reactor Projects Enclosure

SUMMARY

IR 05000275/2017007; 05000323/2017007; 11/13/2017 - 12/27/2017; Diablo Canyon Power

Plant, Units 1 and 2; Temporary Instruction 2515/191, Inspection of the Implementation of Mitigation Strategies and Spent Fuel Pool Instrumentation Orders and Emergency Preparedness Communication/Staffing/Multi-Unit Dose Assessment Plans, issued December 23, 2015.

The inspection covered a one week inspection onsite by three inspectors from the Region IV office and one of the assigned resident inspectors. No findings of significance were identified.

The NRCs program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process, Revision 5.

NRC-Identified and Self-Revealing Findings

None

Licensee-Identified Violations

None

REPORT DETAILS

4OA5 Other Activities (TI 2515/191)

The objective of Temporary Instruction (TI) 2015/191 Inspection of the Implementation of Mitigation Strategies and Spent Fuel Pool Instrumentation Orders and Emergency Preparedness Communication/Staffing/Multi-Unit Dose Assessment Plans is to verify that licensees have adequately implemented the mitigation strategies as described in the licensees Final Integrated Plan (ADAMS Accession No. ML16221A390) and the NRCs plant safety evaluation (ADAMS Accession No. ML16349A386) and to verify that the licensee installed reliable water-level measurement instrumentation in their spent fuel pools. The purpose of this TI is also to verify the licensees have implemented Emergency Preparedness (EP) enhancements as described in their site-specific submittals and NRC safety assessments, including multi-unit dose assessment capability and enhancements to ensure that staffing is sufficient and communications can be maintained during such an event.

The inspection verifies that plans for complying with NRC Orders EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (ADAMS Accession No. ML12229A174) and EA-12-051, Order Modifying Licenses With Regard to Reliable Spent Fuel Pool Instrumentation (ADAMS Accession No. ML12056A044) are in place and are being implemented by the licensee. Additionally, the inspection verifies implementation of staffing and communications information provided in response to the March 12, 2012, request for information letter and multiunit dose assessment information provided per COMSECY-13-0010, Schedule and Plans for Tier 2 Order on Emergency Preparedness for Japan Lessons Learned, dated March 27, 2013 (ADAMS Accession No.

ML12339A262).

The team discussed the plans and strategies with plant staff, reviewed documentation, and where appropriate, performed plant walkdowns to verify that the strategies could be implemented as stated in the licensees submittals and the NRC staff prepared safety evaluation. For most strategies, this included verification that the strategy was feasible, procedures and/or guidance had been developed, training had been provided to plant staff, and required equipment had been identified and staged. Specific details of the teams inspection activities are described in the following sections.

Mitigation Strategies for Beyond-Design-Basis External Events

a. Inspection Scope

The team examined the licensees established guidelines and implementing procedures for the beyond-design-basis mitigation strategies. The team assessed how the licensee coordinated and documented the interface/transition between existing off-normal and Emergency Operating Procedures with the newly developed mitigation strategies. The team selected a number of mitigation strategies, conducted plant walkdowns with licensed operators and responsible plant staff, to assess the adequacy and completeness of the procedures; familiarity of operators with the procedure objectives and specific guidance; staging and compatibility of equipment, and the practicality of the operator actions prescribed by the procedures, consistent with the postulated scenarios.

The team verified that a preventive maintenance program had been established for the FLEX portable equipment and that periodic equipment inventories were in place and being conducted. Additionally, the team examined the introductory and planned periodic/refresher training provided to the Operations and Fire Protection staffs most likely to be tasked with implementation of the FLEX mitigation strategies. The team also reviewed the introductory and planned periodic training provided to the Emergency Response Organization personnel. Documents reviewed are listed in the attachment.

b. Assessment Based on samples selected for review, the inspectors verified that the licensee satisfactorily implemented appropriate elements of the FLEX strategy as described in the plant specific submittals and the associated safety evaluation and determined that the licensee is generally in compliance with NRC Order EA-12-049. The inspectors verified that the licensee satisfactorily:

• Developed and issued FLEX Support Guidelines (FSGs) to implement the FLEX strategies for postulated external events;

• Integrated their FSGs into their existing plant procedures such that entry into and departure from the FSGs are clear when using existing plant procedures;

• Protected FLEX equipment from site-specific hazards;

• Developed and implemented adequate testing and maintenance of FLEX equipment to ensure their availability and capability;

• Trained their staff to assure personnel proficiency in the mitigation of beyond-design-basis events; and

• Developed means to ensure that the necessary off-site FLEX equipment will be available from off-site locations.

The inspectors verified that non-compliances with current licensing requirements, and other issues identified during the inspection were entered into the licensee's corrective action program.

c. Findings

No findings identified.

2. Spent Fuel Pool (SFP) Instrumentation

a. Inspection Scope

The team examined the licensees newly installed spent fuel pool instrumentation.

Specifically, the inspectors verified the sensors were installed as described in the plant specific submittals and the associated safety evaluation and that the cabling for the power supplies and the indications for each channel are physically and electrically separated.

Additionally, environmental conditions and accessibility of the instruments were evaluated. Documents reviewed are listed in the attachment.

b. Assessment Based on samples selected for review, the inspectors determined that the licensee satisfactorily installed and established control of the spent fuel pool instrumentation as described in the plant specific submittals and the associated safety evaluation and determined that the licensee is generally in compliance with NRC Order EA-12-051. The inspectors verified that the licensee satisfactorily:

• Installed the SFP instrumentation sensors, cabling, and power supplies to provide physical and electrical separation as described in the plant specific submittal and safety evaluation;

• Installed the SFP instrumentation display in the location, environmental conditions, and accessibility as described in the plant specific submittals; and

• Trained their staff to assure personnel proficiency with the maintenance, testing, and use of the SFP instrumentation.

The inspectors verified that non-compliances with current licensing requirements, and other issues identified during the inspection were entered into the licensee's corrective action program.

c. Findings

No findings identified.

3. Staffing and Communication Request for Information

a. Inspection Scope

Through discussions with plant staff, review of documentation, and plant walkdowns the team verified that the licensee has implemented required changes to staffing, communications equipment, and facilities to support an Extended Loss of All AC Power (ELAP) scenario as described in the licensees staffing assessment and the NRC safety assessment. The team also verified that the licensee has implemented dose assessment (including releases from spent fuel pools) capability using the licensees site-specific dose assessment software and approach as described in the licensees dose assessment submittal. Documents reviewed are listed in the attachment.

b. Assessment The inspectors reviewed information provided in the licensees multi-unit dose submittal and in response to the NRCs March 12, 2012, request for information letter and verified that the licensee satisfactorily implemented enhancements pertaining to Near-Term Task Force Recommendation 9.3 response to a large scale natural emergency event that results in an extended loss of all ac power to the site and impedes access to the site.

The inspectors verified the following:

• Licensee satisfactorily implemented required staffing change(s) to support an ELAP scenario;

• Emergency preparedness communications equipment and facilities are sufficient for dealing with an ELAP scenario; and

• Implemented dose assessment capabilities (including releases from spent fuel pools) using the licensees site-specific dose assessment software and approach.

The inspectors verified that non-compliances with current licensing requirements, and other issues identified during the inspection were entered into the licensee's corrective action program.

c. Findings

No findings identified.

4OA6 Meetings, Including Exit

Exit Meeting Summary

On November 16, 2017, the inspectors presented the on-site inspection results in a management debrief to Mr. H. Hamzehee, Manager Regulatory Services, and other members of the site staff.

The inspectors completed an exit meeting with Mr. C. Murry, Acting Station Director, and other members of the site staff, via telephone on December 27, 2017, who acknowledged the final results of the inspection. The inspectors confirmed that proprietary information was not provided or examined during the inspection.

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

Licensee Personnel

B. Ashbrook, Security and Emergency Services Manager

M. Baker, Engineering Supervisor

T. Baldwin, Business Initiatives Chief

R. Baradaran, Acting Manager, Regulatory Services

J. Brancheau, Operations Shift Forman

K. Bych, Manager, Engineering

A. Chitwood, Operations Shift Manager

C. Christensen, Emergency Preparedness

W. Conklin, FLEX Engineer

D. Esminger, Chief, Fire Department

M. Frauenheim, Process Improvement Manager

F. Gaber, FLEX Program Owner, Arizona Public Service

S. Guess, Manager, Operations

H. Hamzehee, Manager, Regulatory Services

J. Harker, Manager, Maintenance and Technical Training

S. Kirvin, Manager, Security

S. Leke, Nuclear Operator

D. Madson, Acting Compliance Supervisor

S. Maze, Fukushima Program Supervisor

M. McCoy, NRC Interface, Regulatory Services

J. Morris, Regulatory Services Supervisor

C. Murry, Acting Station Director

A. Peck, Engineering Director

D. Phillips, Security Operations Support

G. Reed, Beyond Design Basis Project Manager

B. Simpson, Manager, Operations Training

A. Sorensen, Regulatory Services Engineer

D. Spaulding, Strategic Projects Contractor

D. Ventresca, Security Operations supervisor

R. Waltos, Assistant engineering Director

A. Warwick, Supervisor, Emergency Planning

T. Wernet, Assistant Chief, Fire Department

D. Yoder, FLEX Engineer

LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED

Closed

Inspection of the Implementation of Mitigation Strategies and Spent Fuel Pool Instrumentation Orders and 2515/191 TI Emergency Preparedness Communication/Staffing/

Multi-Unit Dose Assessment Plans